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| ==SUBJECT:== | | ==SUBJECT:== |
| DOCUMENTATION OF AP600 INFORMAL. CORRESPONDENCE TO WESTINGHOUSE CONCERNING SHUTDOWN PROBABil.lSTIC RISK ASSESSMENT (PRA) AND SEVERE ACCIDENT ISSUES On September 30,1997, and October 16,1997, the staff provided Westinghouse with the e questions in Attachment 1 and 2 respectiv ely. Westinghouse responded to this information informally. Their responses to tho issues can be found la Attachment 3 and 4 respectively. | | DOCUMENTATION OF AP600 INFORMAL. CORRESPONDENCE TO WESTINGHOUSE CONCERNING SHUTDOWN PROBABil.lSTIC RISK ASSESSMENT (PRA) AND SEVERE ACCIDENT ISSUES On September 30,1997, and October 16,1997, the staff provided Westinghouse with the e questions in Attachment 1 and 2 respectiv ely. Westinghouse responded to this information informally. Their responses to tho issues can be found la Attachment 3 and 4 respectively. |
| Subsequent to this information transfer the staff has determined the questions that need to be answered for the final saftty evaluation report (FSER). These questions were sent to Westinghouse in a November 7,1997, letter. The staff considers allissues in Attachment 1 and 2 resolved with the exception of the issues that are identified in the November 7,1997, letter. The November 7,1997, items ?ppear in the open item tracking system (OITS'.f Therefore, no additionalitems from attachment 1 or 2 need to be added to the OITS. | | Subsequent to this information transfer the staff has determined the questions that need to be answered for the final saftty evaluation report (FSER). These questions were sent to Westinghouse in a {{letter dated|date=November 7, 1997|text=November 7,1997, letter}}. The staff considers allissues in Attachment 1 and 2 resolved with the exception of the issues that are identified in the {{letter dated|date=November 7, 1997|text=November 7,1997, letter}}. The November 7,1997, items ?ppear in the open item tracking system (OITS'.f Therefore, no additionalitems from attachment 1 or 2 need to be added to the OITS. |
| Attachment 5 contains information that was sent to Westinghouse on December 10,1997, concerning what the staff believed were l% functional requirements that needed to be incorporated into the Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) for the reactor vesselinsulation design. The resolution of this issue will be documented in the ITAAC and will be %cked under the corresponding FSER open item number in OITS. Attachment 6 contains information that was sent to Westinghouse on December 19,1997, concerning Westinghouse's response to severe accident open items. The resolution of these questions will be tracked with the corresponding FSER open item number in the OITS. | | Attachment 5 contains information that was sent to Westinghouse on December 10,1997, concerning what the staff believed were l% functional requirements that needed to be incorporated into the Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) for the reactor vesselinsulation design. The resolution of this issue will be documented in the ITAAC and will be %cked under the corresponding FSER open item number in OITS. Attachment 6 contains information that was sent to Westinghouse on December 19,1997, concerning Westinghouse's response to severe accident open items. The resolution of these questions will be tracked with the corresponding FSER open item number in the OITS. |
| original signed by: | | original signed by: |
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| ==SUBJECT:== | | ==SUBJECT:== |
| DOCUMENTATION OF AP600 INFORMAL CORRESPONDENCE TO WESTINGHOUSE CONCERNING SHUTDOWN PROBASILISTIC RISK A68ESSMENT (PRA) AND SEVERE ACCIDENT ISSUES On September 30,1997, and October 16,1997, the staff provided Westinghouse with the questions lil Attachment 1 and 2 respectively. Westinghouse responded to this information Informally. Their responses to the issues can be found in Attachment 3 and 4 respectively. | | DOCUMENTATION OF AP600 INFORMAL CORRESPONDENCE TO WESTINGHOUSE CONCERNING SHUTDOWN PROBASILISTIC RISK A68ESSMENT (PRA) AND SEVERE ACCIDENT ISSUES On September 30,1997, and October 16,1997, the staff provided Westinghouse with the questions lil Attachment 1 and 2 respectively. Westinghouse responded to this information Informally. Their responses to the issues can be found in Attachment 3 and 4 respectively. |
| Subsequent to this information transfer the staff has determined the questions that need to be answered for the nnel safety evaluation report (FSER). These questions were sent to Westinghouse in a November 7,1997, letter. The staff considers allissues in Attachment i and 2 resolved whh the exception of the issues that are identified in the November 7,1997, | | Subsequent to this information transfer the staff has determined the questions that need to be answered for the nnel safety evaluation report (FSER). These questions were sent to Westinghouse in a {{letter dated|date=November 7, 1997|text=November 7,1997, letter}}. The staff considers allissues in Attachment i and 2 resolved whh the exception of the issues that are identified in the November 7,1997, |
| ~ letter. The November 7,1997, Hems appear in the open hem tracking system (OITS). Therefore, no additional hems from attachment 1 or 2 nood to be added to the OITS. | | ~ letter. The November 7,1997, Hems appear in the open hem tracking system (OITS). Therefore, no additional hems from attachment 1 or 2 nood to be added to the OITS. |
| Attachment 5 contains information that was sent to Westinghouse on December 10,1997, concerning what the staff believed were the functional requirements that needed to be incorporated into the inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) for the l | | Attachment 5 contains information that was sent to Westinghouse on December 10,1997, concerning what the staff believed were the functional requirements that needed to be incorporated into the inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) for the l |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20216J0681999-09-29029 September 1999 Forwards Rev 3 of AP600 Design Control Document, Incorporating Documentation Changes Resulting from Final Review Performed to Check Consistency of Implementation of Approved Design Change Proposals.With Summary of Changes ML20207G5411999-06-0808 June 1999 Discusses Request Made by Westinghouse on 981109 That Proprietary WCAP-14252,Rev 1,be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20195D5201999-06-0404 June 1999 Discusses Westinghouse Request That Change Pages Submitted on 980921 to WCAP-14292 Be Withheld from Public Disclosure. Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20196G2431999-05-21021 May 1999 Informs That USNRC Has Published in Fr Encl Notice of Proposed Rulemaking Re AP600 Design Certification Rule. Rulemaking Allows Applicants or Licensees to Construct AP600 Std Plant Design by Referencing Design Certification Rule ML20206G5411999-05-0505 May 1999 Forwards Draft Environ Assessment Re Proposed Certification of AP600 Std Plant Design.Environ Assessment Will Be Used as Basis for NRC Finding of No Significant Environ Impact Resulting from Certification of AP600 Design ML20205J3351999-04-0707 April 1999 Informs That USNRC Staff Has Completed Review of Rev 2 of AP600 Design Control Document,Verified That All of Changes in Rev 2 Are Acceptable & Determined That AP600 Dcd,Rev 2, Can Now Be Used in Proposed Design Certification Rule NSD-NRC-99-5827, Forwards Rev 2 to AP600 Design Control Document.Attachment 1 Provides Summary of Changes Made as Part of Mar 1999 Rev to AP600 Design Control Document1999-03-31031 March 1999 Forwards Rev 2 to AP600 Design Control Document.Attachment 1 Provides Summary of Changes Made as Part of Mar 1999 Rev to AP600 Design Control Document ML20205D3051999-03-25025 March 1999 Requests Amend to 920626 Application for Design Certification of AP600,including AP600 Ssar & AP600 Dcd,To Reflect Sale of CBS Commercial Nuclear Business to W ML20203C5481999-02-10010 February 1999 Forwards Rev 1 to AP600 Design Control Document (DCD) for Docket File.Dcd Provides Reference Basis for AP600 Design Certification ML20199H8671999-01-20020 January 1999 Forwards Comments on AP600 Design Control Document,Submitted by Westinghouse ML20199B1121999-01-0707 January 1999 Advises That Info Contained in NSRA-APSL-92-0268 & Containing Presentation Matl Used in 921209-10 Meeting,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA ML20198B4601998-12-14014 December 1998 Discusses W Ltr NTD-NRC-95-4556,dtd 950918,provided as Status Rept on Proprietary Matl Submitted to NRC to Support AP600 Design Review Effort.Proprietary Info in Encl Have Been Removed from AP600 Docket File & Being Returned ML20197G3501998-11-30030 November 1998 Forwards AP600 Design Control Document, Vols 1-12 for Docket File.Submittal Closes Confirmatory Items 1.5-1 & 1.5-2 from Sept 1998 Final SER Re Certification of AP600 Std Design ML20195E9331998-11-0909 November 1998 Requests That Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept, Vols I- Iv,Be Withheld (Ref 10CFR2.790) NSD-NRC-98-5806, Forwards non-proprietary Rev 1 to WCAP-14253 & Proprietary Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept. Proprietary Rept Includes Vols 1-4.Proprietary Info Withheld,Per 10CFR2.7901998-11-0909 November 1998 Forwards non-proprietary Rev 1 to WCAP-14253 & Proprietary Rev 1 to WCAP-14252, AP600 Low-Pressure Integral Sys Test at or State Univ Final Data Rept. Proprietary Rept Includes Vols 1-4.Proprietary Info Withheld,Per 10CFR2.790 ML20155G9021998-11-0303 November 1998 Advises That Info Contained in 981012 ltr,NSD-NRC-98-5795, Will Be Withheld from Public Disclosure,Per 10CFR2.790(b) (5) & Section 103(b) of AEA of 1954,as Amended ML20155G9271998-11-0202 November 1998 Forwards Copy of NRC Staff FSER for Westinghouse AP600 Design.Staff Completed Review of Design & Issued Final Design Approval & FSER on 980903.Without Encl ML20155G7591998-11-0202 November 1998 Forwards Copy of NRC Staff FSER for Westinghouse AP600 Design,Per Discussion at Sept 1997 Meeting.Staff Completed & Issued Final Design Approval of FSER on 980903.Without Encl NSD-NRC-98-5795, Informs That Figures from Rev 0 & Rev 3 of PRA Which Indicate Location of H Igniters Should Be Considered Proprietary.Nonproprietary Versions of AP600 General Arrangement Drawings Were Provided in Rev 7 of Ssar1998-10-12012 October 1998 Informs That Figures from Rev 0 & Rev 3 of PRA Which Indicate Location of H Igniters Should Be Considered Proprietary.Nonproprietary Versions of AP600 General Arrangement Drawings Were Provided in Rev 7 of Ssar ML20154A4091998-09-29029 September 1998 Advises That Certain Info Contained in Westinghouse Ltr NTD-NRC-95-4506,dtd 950713,submitting WCAP-14425,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5).Figure 3-1 Will Be Placed Into Public Record ML20153G2521998-09-25025 September 1998 Advises That Proprietary Matl Discovered by NRC in NSD-NRC-97-4966 & Proprietary Matl Noted by W in NSD-NRC-98-5772 Will Be Withhheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20153C1001998-09-15015 September 1998 Advises That Matls Re AP600 Notrump Final Validation Rept, WCAP-14807,marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended NSD-NRC-98-5788, Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period of 980702-0826.Index of Encl Matl Provided1998-09-15015 September 1998 Forwards Formal Transmittal of Correspondence Previously Sent Informally Over Period of 980702-0826.Index of Encl Matl Provided ML20151X4381998-09-15015 September 1998 Informs That Staff Has Decided to Accept Claim That Info in WCAP-14135,Rev 1 Is Proprietary & Will Be Withheld from Public Disclosure,Per W 980821 & 26 Ltrs ML20151X4041998-09-11011 September 1998 Discusses Revised Tier 2 Info for AP600 Design.Staff Revised Decision on Whether Fire Protection Should Expire at First Full Power Encl ML20151V1711998-09-0808 September 1998 Advises That Info Re Westinghouse AP600 Std Safety Analysis Rept Through Rev 4 & PRA Through Rev 5 Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5).Disposition of Ssar & PRA Proprietary Info Encl ML20151V2231998-09-0808 September 1998 Informs That NRC Determined That WCAP-14132 Encl in Westinghouse Ltr NTD-NRC-94-4244,dtd 940729 & Marked as Proprietary,Will Be Withheld from Public Disclosure,Per to 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20151S9181998-09-0303 September 1998 Advises That Info Marked as Proprietary Re Westinghouse AP600 Design Ltrs Concerning Pxs Scaling & Pirt Closure Rept WCAP-14727,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20239A1481998-09-0303 September 1998 Forwards Notice of Issuance of Final Design Approval & Final SER for AP600.FDA Allows AP600 Design to Be Referenced in Application for Construction Permit or Operating License Under 10CFR50 or Application for Combined License ML20239A3111998-09-0303 September 1998 Forwards Final SER Which Summarizes Staff Safety Review of AP600 Design Against Requirements of Subpart B of 10CF5R52 & Delineates Scope of Technical Details Considered in Evaluating Proposed Design ML20151V8521998-09-0101 September 1998 Extends Invitation to Attend Ceremony on 980911,where NRC Will Present Final Design Approval for AP600 Std Nuclear Reactor Design to Westinghouse NSD-NRC-98-5781, Informs That W Determined That AP600 FSER Contains No Proprietary Info1998-09-0101 September 1998 Informs That W Determined That AP600 FSER Contains No Proprietary Info ML20151V2201998-08-31031 August 1998 Informs That EPRI Documents, GOTHIC Containment Analysis Package Qualification Rept, GOTHIC Containment Analysis Qualification Manual, & Listed Documents Dtd Sept 1993 Will Be Withheld from Public Disclosure ML20151V8431998-08-31031 August 1998 Extends Invitation to Attend Ceremony on 980911,where NRC Will Present Final Design Approval for AP600 Std Nuclear Reactor Design to Westinghouse ML20238F3241998-08-31031 August 1998 Advises That AP600 RAI Responses Encl in Westinghouse Ltrs NTD-NRC-95-4598,dtd 951117,as Modified by NSD-NRC-98-5776, Dtd 980826,marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) ML20238F5991998-08-31031 August 1998 Refers to W 980821 Revised Response to Insp Rept 99900404/97-01 That Contained All Substantive Info Provided w/DCP/NRC-1074 Ltr.Nrc Will Destroy DCP/NRC-1074,as Requested NSD-NRC-98-5783, Forwards non-proprietary Rev 2 to WCAP-14989, Accident Specification & Phenomena Evaluation for AP600 Passive Containment Cooling Sys1998-08-28028 August 1998 Forwards non-proprietary Rev 2 to WCAP-14989, Accident Specification & Phenomena Evaluation for AP600 Passive Containment Cooling Sys NSD-NRC-98-5782, Forwards Corrected Pages 4-28 Through 4-32 to Be Inserted in Rev 2 to non-proprietary WCAP-14953, AP600 Pxs Scaling & Pirt Closure Rept. Pages Were Originally Submitted W/Incorrect Header Which Stated 'W Proprietary Class 2.'1998-08-28028 August 1998 Forwards Corrected Pages 4-28 Through 4-32 to Be Inserted in Rev 2 to non-proprietary WCAP-14953, AP600 Pxs Scaling & Pirt Closure Rept. Pages Were Originally Submitted W/Incorrect Header Which Stated 'W Proprietary Class 2.' NSD-NRC-98-5778, Provides Commitment to Include Requested Changes Into AP600 Design Control Document.Discussion W/Vijuk on 980825 Re Disposition of Ltrs DCP/NRC1074,dtd 971016 & DCP/NRC1324,dtd 980403,formalized1998-08-27027 August 1998 Provides Commitment to Include Requested Changes Into AP600 Design Control Document.Discussion W/Vijuk on 980825 Re Disposition of Ltrs DCP/NRC1074,dtd 971016 & DCP/NRC1324,dtd 980403,formalized ML20237E4421998-08-27027 August 1998 Advises That Info Contained in Ltr DCP/NRC-0985,dtd 970821, Sought to Be Withheld,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended NSD-NRC-98-5777, Provides Revised Response to NRC Ltr Re W Requests for Withholding Info Re AP600 PCS Final Data rept,WCAP-14135 & WCAP-141381998-08-26026 August 1998 Provides Revised Response to NRC Ltr Re W Requests for Withholding Info Re AP600 PCS Final Data rept,WCAP-14135 & WCAP-14138 NSD-NRC-98-5776, Forwards Proprietary Revised Response to Ref NRC Ltr Re W Requests for Withholding Info Re AP600 Design Certification Test Program,Notrump Computer Code,Wcobra/Trac Computer Code & Loftran Computer Code.Proprietary Info Withheld1998-08-26026 August 1998 Forwards Proprietary Revised Response to Ref NRC Ltr Re W Requests for Withholding Info Re AP600 Design Certification Test Program,Notrump Computer Code,Wcobra/Trac Computer Code & Loftran Computer Code.Proprietary Info Withheld ML20237E0731998-08-26026 August 1998 Advises That Info in WCAP-14812,revs 1 & 2, Accident Spec & Phenomena Evaluation for AP600 PCS, Will Be Withheld from Public Disclosure ML20238F8031998-08-26026 August 1998 Requests That Proprietary W Revised Response to NRC Ltrs Re Requests for Withholding Info,Be Withheld from Public Disclosure IAW 10CFR2.790 NSD-NRC-98-5774, Informs That W Faxed Last Response Re Afser Open Item 1.1-1 to NRC on 980821.Last of Attachments Supporting Several of Responses Faxed to NRC Over Past Several Days Were Express Mailed to NRC on 980821.Responses Close Subject Open It1998-08-24024 August 1998 Informs That W Faxed Last Response Re Afser Open Item 1.1-1 to NRC on 980821.Last of Attachments Supporting Several of Responses Faxed to NRC Over Past Several Days Were Express Mailed to NRC on 980821.Responses Close Subject Open Item NSD-NRC-98-5773, Responds to Questions Raised in NRC 971022 & s Re Proprietary Info Contained in 970930 Summary of Meeting Held on 970804-15 Concerning Structural Design of AP600.Figure 12-24 of WCAP-14407 Still Considered Proprietary by W1998-08-21021 August 1998 Responds to Questions Raised in NRC 971022 & s Re Proprietary Info Contained in 970930 Summary of Meeting Held on 970804-15 Concerning Structural Design of AP600.Figure 12-24 of WCAP-14407 Still Considered Proprietary by W ML20237E7991998-08-21021 August 1998 Forwards non-proprietary Results of AP600 Design Assurance Review (Dar) That Was Commitment in W Response to NRC Insp Rept 99900404/97-02.Info Should Assist in Closing Nonconformances & Unresolved Item Identified in Insp Rept NSD-NRC-98-5771, Forwards non-proprietary Rev 2 to WCAP-14138, Final Data Rept for PCS Large-Scale Tests,Phase 2 & Phase 3. Submittal Satisfies Verbal Commitment to Revise non-proprietary Version of PCS Final Data Rept Made by W1998-08-21021 August 1998 Forwards non-proprietary Rev 2 to WCAP-14138, Final Data Rept for PCS Large-Scale Tests,Phase 2 & Phase 3. Submittal Satisfies Verbal Commitment to Revise non-proprietary Version of PCS Final Data Rept Made by W NSD-NRC-98-5769, Responds to NRC Ref Ltrs Re W Requests for Withholding Info. Info Provided as Proprietary in Ref 1 Has Either Been Moved from Ssar to Ref 3,which Includes non-proprietary Version of Rept or Made non-proprietary in Current Version of1998-08-21021 August 1998 Responds to NRC Ref Ltrs Re W Requests for Withholding Info. Info Provided as Proprietary in Ref 1 Has Either Been Moved from Ssar to Ref 3,which Includes non-proprietary Version of Rept or Made non-proprietary in Current Version of Ssar NSD-NRC-98-5772, Forwards non-proprietary & Proprietary Info in Response to NRC Ltrs Re W Requests for Withholding Info.Separate Ltr & Affidavit Justifying Proprietary Nature of Info,Encl. Proprietary Info Withheld,Per 10CFR2.7901998-08-21021 August 1998 Forwards non-proprietary & Proprietary Info in Response to NRC Ltrs Re W Requests for Withholding Info.Separate Ltr & Affidavit Justifying Proprietary Nature of Info,Encl. Proprietary Info Withheld,Per 10CFR2.790 1999-09-29
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20207G5411999-06-0808 June 1999 Discusses Request Made by Westinghouse on 981109 That Proprietary WCAP-14252,Rev 1,be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20195D5201999-06-0404 June 1999 Discusses Westinghouse Request That Change Pages Submitted on 980921 to WCAP-14292 Be Withheld from Public Disclosure. Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20196G2431999-05-21021 May 1999 Informs That USNRC Has Published in Fr Encl Notice of Proposed Rulemaking Re AP600 Design Certification Rule. Rulemaking Allows Applicants or Licensees to Construct AP600 Std Plant Design by Referencing Design Certification Rule ML20206G5411999-05-0505 May 1999 Forwards Draft Environ Assessment Re Proposed Certification of AP600 Std Plant Design.Environ Assessment Will Be Used as Basis for NRC Finding of No Significant Environ Impact Resulting from Certification of AP600 Design ML20205J3351999-04-0707 April 1999 Informs That USNRC Staff Has Completed Review of Rev 2 of AP600 Design Control Document,Verified That All of Changes in Rev 2 Are Acceptable & Determined That AP600 Dcd,Rev 2, Can Now Be Used in Proposed Design Certification Rule ML20199H8671999-01-20020 January 1999 Forwards Comments on AP600 Design Control Document,Submitted by Westinghouse ML20199B1121999-01-0707 January 1999 Advises That Info Contained in NSRA-APSL-92-0268 & Containing Presentation Matl Used in 921209-10 Meeting,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA ML20198B4601998-12-14014 December 1998 Discusses W Ltr NTD-NRC-95-4556,dtd 950918,provided as Status Rept on Proprietary Matl Submitted to NRC to Support AP600 Design Review Effort.Proprietary Info in Encl Have Been Removed from AP600 Docket File & Being Returned ML20155G9021998-11-0303 November 1998 Advises That Info Contained in 981012 ltr,NSD-NRC-98-5795, Will Be Withheld from Public Disclosure,Per 10CFR2.790(b) (5) & Section 103(b) of AEA of 1954,as Amended ML20155G7591998-11-0202 November 1998 Forwards Copy of NRC Staff FSER for Westinghouse AP600 Design,Per Discussion at Sept 1997 Meeting.Staff Completed & Issued Final Design Approval of FSER on 980903.Without Encl ML20155G9271998-11-0202 November 1998 Forwards Copy of NRC Staff FSER for Westinghouse AP600 Design.Staff Completed Review of Design & Issued Final Design Approval & FSER on 980903.Without Encl ML20154A4091998-09-29029 September 1998 Advises That Certain Info Contained in Westinghouse Ltr NTD-NRC-95-4506,dtd 950713,submitting WCAP-14425,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5).Figure 3-1 Will Be Placed Into Public Record ML20153G2521998-09-25025 September 1998 Advises That Proprietary Matl Discovered by NRC in NSD-NRC-97-4966 & Proprietary Matl Noted by W in NSD-NRC-98-5772 Will Be Withhheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20151X4381998-09-15015 September 1998 Informs That Staff Has Decided to Accept Claim That Info in WCAP-14135,Rev 1 Is Proprietary & Will Be Withheld from Public Disclosure,Per W 980821 & 26 Ltrs ML20153C1001998-09-15015 September 1998 Advises That Matls Re AP600 Notrump Final Validation Rept, WCAP-14807,marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20151X4041998-09-11011 September 1998 Discusses Revised Tier 2 Info for AP600 Design.Staff Revised Decision on Whether Fire Protection Should Expire at First Full Power Encl ML20151V1711998-09-0808 September 1998 Advises That Info Re Westinghouse AP600 Std Safety Analysis Rept Through Rev 4 & PRA Through Rev 5 Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5).Disposition of Ssar & PRA Proprietary Info Encl ML20151V2231998-09-0808 September 1998 Informs That NRC Determined That WCAP-14132 Encl in Westinghouse Ltr NTD-NRC-94-4244,dtd 940729 & Marked as Proprietary,Will Be Withheld from Public Disclosure,Per to 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20151S9181998-09-0303 September 1998 Advises That Info Marked as Proprietary Re Westinghouse AP600 Design Ltrs Concerning Pxs Scaling & Pirt Closure Rept WCAP-14727,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20239A3111998-09-0303 September 1998 Forwards Final SER Which Summarizes Staff Safety Review of AP600 Design Against Requirements of Subpart B of 10CF5R52 & Delineates Scope of Technical Details Considered in Evaluating Proposed Design ML20239A1481998-09-0303 September 1998 Forwards Notice of Issuance of Final Design Approval & Final SER for AP600.FDA Allows AP600 Design to Be Referenced in Application for Construction Permit or Operating License Under 10CFR50 or Application for Combined License ML20151V8521998-09-0101 September 1998 Extends Invitation to Attend Ceremony on 980911,where NRC Will Present Final Design Approval for AP600 Std Nuclear Reactor Design to Westinghouse ML20151V2201998-08-31031 August 1998 Informs That EPRI Documents, GOTHIC Containment Analysis Package Qualification Rept, GOTHIC Containment Analysis Qualification Manual, & Listed Documents Dtd Sept 1993 Will Be Withheld from Public Disclosure ML20151V8431998-08-31031 August 1998 Extends Invitation to Attend Ceremony on 980911,where NRC Will Present Final Design Approval for AP600 Std Nuclear Reactor Design to Westinghouse ML20238F5991998-08-31031 August 1998 Refers to W 980821 Revised Response to Insp Rept 99900404/97-01 That Contained All Substantive Info Provided w/DCP/NRC-1074 Ltr.Nrc Will Destroy DCP/NRC-1074,as Requested ML20238F3241998-08-31031 August 1998 Advises That AP600 RAI Responses Encl in Westinghouse Ltrs NTD-NRC-95-4598,dtd 951117,as Modified by NSD-NRC-98-5776, Dtd 980826,marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) ML20237E4421998-08-27027 August 1998 Advises That Info Contained in Ltr DCP/NRC-0985,dtd 970821, Sought to Be Withheld,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20237E0731998-08-26026 August 1998 Advises That Info in WCAP-14812,revs 1 & 2, Accident Spec & Phenomena Evaluation for AP600 PCS, Will Be Withheld from Public Disclosure ML20237C4801998-08-20020 August 1998 Informs That Staff Will Withhold from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended, Presentation Matl from 970212-14 ACRS Meeting Encl in W Ltr NSD-NRC-98-5744 Dtd 980803,until Policy Matter,Clarified ML20237D4391998-08-18018 August 1998 Confirms Phone Conversation Between NRC & W Re Submittal of Final Portions of Documentation Necessary to Complete Review & Issue Final SER & Final Design Approval for AP600 ML20236V6671998-07-30030 July 1998 Advises That Info Contained in WCAP-14601,rev 2,submitted in Westinghouse Ltr NSD-NRC-98-5712,dtd 980616 & Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20236V8621998-07-30030 July 1998 Informs That Proprietary Info Encl in Westinghouse Ltr NSD-NRC-98-5736,dtd 980713 Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20236U7811998-07-29029 July 1998 Advises That WCAP-14270,rev 1, AP600 LP Integral Sys Test Facility Scaling Rept, Encl in Ltr NSD-NRC-98-5718,dtd 980619 & Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA ML20236U7831998-07-29029 July 1998 Informs That Certain Info in AP600 Ssar,If Proposed for Change That Refs AP600 Std Design,Will Require Prior NRC Approval Before Proposed Change Can Be Implemented.Tier 2* Info for AP600 Design & Staff Decision Encl ML20236U8131998-07-29029 July 1998 Advises That WCAP-14471,rev 0, Steam Condensation Events at Osu AP600 Facility Submitted in Ltr NSD-NRC-96-4661,dtd 960306 & Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA ML20236V0511998-07-29029 July 1998 Informs That AP600 Boron Dilution Transient Analysis Encl in Westinghouse Ltrs NSD-NRC-96-4792,dtd 960808 & NSD-NRC-98-5739,dtd 980720 & Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790 ML20236V0411998-07-28028 July 1998 Discusses Return of Proprietary Matl to Westinghouse Docketed Under AP600 Design Review.Proprietary Documents Listed in Encl 1 Removed from AP600 File & Returned for Disposition or Retention ML20236T3101998-07-22022 July 1998 Discusses W 941031 Submittal by Ltr (NTD-NRC-94-4330) of AP600 Notrump Core Makeup Tank Preliminary Validation Rept & Requests That Info Be Withheld from Public Disclosure. Determined Info Proprietary & Will Be Withheld from Public ML20236T4091998-07-22022 July 1998 Informs That Info Related to Wgothic lumped-parameter & Distributed Parameter Nodalization of AP600 & Wgothic Heat Sink & Flow Path Description Including Areas,Thickness & Evaluations Will Be Withheld,Per 10CFR2.790(b)(5) & 103(b) ML20236T1691998-07-22022 July 1998 Advises That Proprietary Matl Encl in NSD-NRC-96-4700,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)5) & Section 103(b) of AEA of 1954,as Amended ML20236T1361998-07-22022 July 1998 Advises That Info Contained in TRs WCAP-12945-P-A & WCAP-14747,respectively Submitted in Ltr NTD-NRC-95-4406, Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEC of 1954,as Amended ML20236T0591998-07-22022 July 1998 Informs That Staff Plans to Return NSD-NRC-96-4762, NSD-NRC-96-4763,NSD-NRC-96-4790,... Transmittals to Westinghouse W/O Proprietary Determination,Due to Info Being Provided in Documents Submitted at Later Date ML20236S9841998-07-22022 July 1998 Informs That Staff Plans to Return NSD-NRC-94-4246, NSD-NRC-94-4327 & NSD-NRC-94-4318 Transmittals to Westinghouse W/O Proprietarty Determination,Due to Info Being Provided in Documents Submitted at Later Date ML20236S9621998-07-22022 July 1998 Advises That Info in NSD-NRC-97-5424 on AP600 Passive Containment Cooling Sys Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20236S9321998-07-22022 July 1998 Advises That Info in on AP600 Large Scale Test Facility Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20236S9131998-07-22022 July 1998 Informs That WCAP-14776 (Rev 2) Encl in Westinghouse Ltr NSD-NRC-97-5202,dtd 970620 Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20236S1601998-07-22022 July 1998 Informs That Encl Table,Associated W/Westinghouse AP600 Ltrs,Will Be Marked as Proprietary & Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20236S1511998-07-22022 July 1998 Informs That Matl Encl in NTD-NRC-94-4215 & NTD-NRC-95-4436, Marked as Proprietary,Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20236S1431998-07-22022 July 1998 Informs That Encl Table Associated W/Westinghouse AP600 Design Ltrs Will Be Marked as Proprietary & Will Be Withheld from Public Disclosure Pursuant 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20236S1321998-07-22022 July 1998 Informs That Matls Documented in Encl Table,Associated W/Westinghouse AP600 WCAPs Submitted in Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended 1999-06-08
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,f g* January 7,1998 APPLICANT: Westinghouse Electric Corporation PROJECT: AP600
SUBJECT:
DOCUMENTATION OF AP600 INFORMAL. CORRESPONDENCE TO WESTINGHOUSE CONCERNING SHUTDOWN PROBABil.lSTIC RISK ASSESSMENT (PRA) AND SEVERE ACCIDENT ISSUES On September 30,1997, and October 16,1997, the staff provided Westinghouse with the e questions in Attachment 1 and 2 respectiv ely. Westinghouse responded to this information informally. Their responses to tho issues can be found la Attachment 3 and 4 respectively.
Subsequent to this information transfer the staff has determined the questions that need to be answered for the final saftty evaluation report (FSER). These questions were sent to Westinghouse in a November 7,1997, letter. The staff considers allissues in Attachment 1 and 2 resolved with the exception of the issues that are identified in the November 7,1997, letter. The November 7,1997, items ?ppear in the open item tracking system (OITS'.f Therefore, no additionalitems from attachment 1 or 2 need to be added to the OITS.
Attachment 5 contains information that was sent to Westinghouse on December 10,1997, concerning what the staff believed were l% functional requirements that needed to be incorporated into the Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) for the reactor vesselinsulation design. The resolution of this issue will be documented in the ITAAC and will be %cked under the corresponding FSER open item number in OITS. Attachment 6 contains information that was sent to Westinghouse on December 19,1997, concerning Westinghouse's response to severe accident open items. The resolution of these questions will be tracked with the corresponding FSER open item number in the OITS.
original signed by:
Joseph M. Sebrosky, Project Manager Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003 Attachments: As stated )
cc w/atts: See next page DISTRIEL)JJQ.[f i See next page g i
DOCUMENT NAME: A:\FA(PRA. SUM To receive a copy of this document, Indicate in the box: *C"
- Copy withe... a;tachment/ enclosure *E" = Copy w;th attachment / enclosure "N" = No copy OFFICE PM:PDST:DRPM l SCSB:DSSA SPSB:DSSA C D.PDST:DRPM NAME JMSeorosky:s0 A ffr RPalla N[/' MPohida h\ttf) Th Ouay M '
DATE 01/(fl98 // 01/ 7/98 01/4 /98 01/7 /98 MfF 9001150205 900107 PDR ADOCK 05200003 E PDR
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[ NUCLEAR REGULATORY COMMisslON s ,
waswewetow, o.c. seeewem January 7. 1998 APPLICANT: Westinghouse Electric Corporation PROJECT: AP600
SUBJECT:
DOCUMENTATION OF AP600 INFORMAL CORRESPONDENCE TO WESTINGHOUSE CONCERNING SHUTDOWN PROBASILISTIC RISK A68ESSMENT (PRA) AND SEVERE ACCIDENT ISSUES On September 30,1997, and October 16,1997, the staff provided Westinghouse with the questions lil Attachment 1 and 2 respectively. Westinghouse responded to this information Informally. Their responses to the issues can be found in Attachment 3 and 4 respectively.
Subsequent to this information transfer the staff has determined the questions that need to be answered for the nnel safety evaluation report (FSER). These questions were sent to Westinghouse in a November 7,1997, letter. The staff considers allissues in Attachment i and 2 resolved whh the exception of the issues that are identified in the November 7,1997,
~ letter. The November 7,1997, Hems appear in the open hem tracking system (OITS). Therefore, no additional hems from attachment 1 or 2 nood to be added to the OITS.
Attachment 5 contains information that was sent to Westinghouse on December 10,1997, concerning what the staff believed were the functional requirements that needed to be incorporated into the inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) for the l
reactor vesselinsulation design. The resolution of this issue will be documented in the ITAAC and will be tracked under the corresponding FSER open item number in OITS. Attachment 6 contains information th41 was sont to
- Vestinghouse on December 19,1997, concoming Westinghowe's respon6e to severe accident open items. The resolution of these questions will be tracked with the corresponding FSER open item nu bor in the OITS.
jJ eph M. Sobrosky, Pr et Manager s Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003 Attachments: As statwd cc w/atts: See n9xt page -
s i
Westinghouse Electdc Corporation Docket No. 52 003 l i
[
oc: Mr. Nicholas J. Liparuto, Manspor Mr. Frank A. Ross !
Nuclear Safety and Repuistory Analysis U.S. Department of Energy, NE-42 l 4
Nucear and Advanced Technology Division Offloe of LWR Safety and Technology i Westinghouse Electric Corporation 19901 Germantown Road l P.O. Box 355 - Germantown, MD 20074 :
PMtsburgh, PA 15230 l Mr. Russ Bell i Mr. B. A. McIntyre Senior Project Manager, Programs ,
Advanood Plant Safety & Lloonsing Nuclear Energy institute !
Westinghouse Electric Corporation 1776 i Street, NW !
Energy Systems Busines6 UnN SuNe300 t Box 365 Washingten, DC 20006 3708 l PWtaburgh, PA 15230 :
Ms. Lynn Connor !
Ms. Cindy L. Haag Doc Soarch Associates ,
Advanced Plant Safety & Licensing Post Office Box 34 Westinghouse Electric Corporation Cabin John, MD 20818 ;
Energy Systems Business UnN ;
Box 355 Dr. Craig D. Sawyer, Manager Pittsburgh, PA 15230 Advanced Reactor Prcyems ;
GE N# ear Energy l Mr. M. D. Beaumord 175 Curtner Avenue, MC 754 Nuclear and Advanced Technology Division San Joe, CA 95125 Westinghouse Electate Corporation One Montrose Metro Mr. Rober1 H. Suchheir 11921 Rockvil6e Pike GE Nuclear Energy ;
Suite 350 175 Curtner Avenue. MC 781 ,
Rockvil64, MD 20852 San Jose, CA 95125 !
Mr. Storiing Franks Barton Z. Cowan, Esq. .;
U.S. Department of Energy Eckert Seamans Cherin & Mellott ,
NE50 600 Grant Street 42nd Floor i 19901 Germantown Road Pittsburgh, PA 15219 ,
Germantown, MD 20074 Mr. Ed Rodwell, Mana9er :
Mr. Cheries Thompson, Nuclear Engineer PWR Design Certificatien !
AP600 Certification Electric Power Research Instituto NE50 3412 Hillview Avenue !
- 19901 Germantown Road Palo Aho, CA 94303 Germantown, MD 20874 4
, Mr. Robert Malers, P.E.-
Pennsylvania Department of
- Environmental Protection Bureau of Radiation Protection <
- Hachel Carson State Offlos Building P.O. Box 6469 Harrisburg, PA 17105-6469.
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Dl8TRIBUTION w/ attachments:
Docket File PUBLIC PDST R/F TKenyon -
BHuffman JSebrosky DScaletti JNW61oon DISTRIBUTION w/o attachment 4:
Scollins/FM6raglia 012 G18 BSheron,012 GIS ,
RZimmerman,012 G18 ,
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- 4 DMatthews TQuay - ' '
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Comments sent to Westinghouse on September 30,1997 Regarding the Shutdown PRA
{
- 1. Based on item 1 of attachment 6 of the Sept 9mber 18th letter, we requested Westinghouse f to generate a revised shutJown CDF, a revised list of dominant cutsets, and revised ;
importance analyses assuming the AP600 design changes assumed in Attachment 54A of the shutdown PRA and the new success criteria (incorporation of 4th stage ADS valves to preclude surge line flooding). As I look at the revised CDF estimate (case 1) dated .
September 26,1997, common cause failure of the IRWST MOVs appears in the second largest cutset. There are no IRWST squibs appearing in the dominant cutsets as in Appendix 54A.
- 2. Based on item 4 of attachment 6 of the September 18th letter, we requested Westinghouse to generated a revised shutdown CDF assuming minimal compliance with TS which assumes: 1 out of 2 IRWST gravity injection paths are inoperable,2 out of 4 ADS valves are inoperable, and RNS V 23 is inoperable. Instead, in case 3 (the TS case), RNS V 23 is credited, and it appears in the top cutset.
Attachment 1
P Comments sont to Westinghouse on October 18,1997, Concerning the Ootober 8,1997 Version of the Shutdown PRA TOPICS FOR DISCUSSION WITH WESTINGHOUSE [
SUCCESS CRITERIA ISSUES In Chapter 54 of the shutdown PRA, W reported that
- recirculation is not required within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after gravity injection. Given 4th stege ADS actuation .
is required during reduced inventory conditions, W la requested to determine when recirculation !
could be initiated.
REPORTING ISSUES j
- 1. The PRA resuHs confeined in Section 6.1 of the Shutdown Evaluation Report need to be !
corrected because they are based on en old version of the shutdown PRA that excludes 4th stage ADS actuation during reduced inventory conditions.
- 2. The PRA results contained in Chapter 5g of the PRA need to be corrected for the same '
reason discussed above. ;
- 3. Attachment 54B needs to document that this attachment contains a re quantification of the baseline and focused shutdown PRA. Given this new success criteria change, W should ;
clearly document that the results of Attachment 548 should be used to derive insights as
^
opposed to the results reported in Attachment 54A or Chapter 54. -
- 4. The results given in 548.1.1 need to be identified as the Baseline Shutdown PRA CDF. It is not a sensitivity study. The results given in 54.b.1.2 need to be identified as the base line Focused Shutdown PRA CDF.
- 5. Two new ADS fault trees were constructed. The success criteria summary tables for these fault trees were provided in the package. However, the fault trees were not submitted. The etaff requests Westinghouse to provide the fault trees and a description of the basic events.
- 6. The description (on page 5 of Attachment B) of how the CCF failure estimates were derived is unclear. According to chapter 5g (page 2g 11), for sensitivity case 3, ADX EV SA should be 5.8E-4 * .1 = 5.8E 5. Westinghouse needs to document how the failure rate for the IWX MV G01 was estimated. Based on Chapter 5g,it appears that IWX MV G01 should be 5 8E-4 * .15 5.8E 5 Westinghouse needs to document how the IWX-CV AO was estimated. Based on the full power PRA, IWX CV AO should be 5.1E 5 per demand.
- 7. Westinghouse needs to document in $4B whether the truncation limits used for the baseline shutdown PRA and the focused shutdown PRA estimates reported in 54.B.1 were also used for the revision 6 of the shutdown PRA.
Attachment 2
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. 2
- 8. Westinghouse needs to document in Section M.b.2 that gravity ir#ction now requires IRC and power to operate during safe shutdown. Westinghouse needs to document in Section 54.5.2 why H is acceptable not to model this new dependency.
- 9. Westinghouse needs to document in Section 54.5. 2 that litWST MOVs 121A and B are no longer required to isolate the IRWST and operate to provide IRWST when called upon.
Squib valves 123a/b and 125/ab are now required to provide IRWST injection when called upon.
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